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The fast-deployable radiation monitoring system (BR ASKRO) is intended for the operational creation of a local autonomous automated network of portable radiation monitoring posts in places where radiation emergencies occur. The main purpose of the system being created is continuous radiation monitoring, on areas up to 1 km2, when performing work to localize accidents and eliminate their consequences to ensure the safe operation of personnel of emergency rescue units, as well as to monitor the effectiveness of the work performed.

The possibility of a qualitative assessment of the current radiation situation - continuously and under any conditions. You can put the device in your pocket, purse, etc. and forget about it. If you get into the zone of radioactive exposure, the alarm will immediately remind you of yourself and let you know about the danger with light and sound signals; The presence of light and sound alarms about the emergency level of radiation hazard; Durable body is made of cast duralumin; Protected by the copyright certificate, the original power supply circuit, which provides low current consumption, allows you to keep the device constantly on and instantly determine whether it enters the zone of radioactive danger; The possibility to operate the device without replacing the battery for a year or more.

▪ Measurements without sampling in geometry 4π ▪ Intelligent detection unit in an airtight container ▪ The possibility of further detailed processing of the measured data using specialized software

Building a flexible and reliable multi-channel system Independent measurements on each channel in a wide range of gamma and neutron radiation dose rates and neutron and beta particle flux densities Audiable and light alarms High reliability and self-control Software that allows you to display on the PC monitor the current radiation situation in the controlled area Data logging Backup power supply The possibility of integration with external security systems

A low-background alpha-beta radiometer with a silicon detector, widely used for measuring small activities. It is recommended for measuring the total alpha and beta activity of natural and drinking waters, as well as for measuring the activity of alpha-emitting radionuclides by spectrometric method. Purpose: measurement of the total activity of alpha-emitting nuclides in "thick" and "thin" counting samples of environmental objects; measurement of the total activity of beta-emitting nuclides in counting samples of soil samples, water samples, air filters and samples obtained by selective radiochemical extraction; measurement of alpha activity of nuclides in counting samples obtained after radiochemical preparation by radiometric method (if available); measurement of alpha activity of nuclides in counting samples obtained after radiochemical preparation by the spectrometric method (if there are techniques and a set of spectrometric "UMF - Spectrum").

Purpose: measurement of the power of ambient dose equivalent (MAED) and ambient dose equivalent (ED) of photon radiation; operational search for sources of ionizing radiation and radioactive materials; measurement of the flux density and fluence of alpha and beta radiation; measurement of surface alpha and beta activity; measurement of the ambient dose equivalent (MAED) power of neutron radiation.

The filter holder FD-05D is designed to install aerosol and iodine filters in it, in an amount of up to 8 pieces. The filters are arranged sequentially. It is used in sampling systems of gas-aerosol media at radiation-hazardous and other production facilities.

The installation is intended for use in gas-aerosol emission control systems in order to determine the volumetric air flow in ventilation systems by measuring the linear air flow velocity at local points of the dimensional section, as well as for measuring air temperature and humidity at local points. The measuring system of the installation complies with GOST 12.3.018-79 (SSBT. Ventilation systems. Methods of aerodynamic tests).

Purpose: measurement of individual dose equivalent (IED) of mixed gamma-neutron radiation; measurement of individual dose equivalent (IED) of neutron radiation;

Transmission of units of absorbed dose, directed, individual dose equivalents and their beta radiation power as part of the working standard of absorbed dose (PD) and absorbed dose power (MPD) of beta radiation in a tissue equivalent substance. ▪ Use of closed radionuclide beta radiation sources 90Sr+90Y (BIS-50, 22 GBk), 85Kr (KAC.D3, 15 GBk) and 147Pm (BIP-50, 10 GBk) ▪ Formation of a reference field from sources by a mobile emitter unit using smoothing filters ▪ Source holders with shutter and protective screens ▪ Calibrated length rods and laser device for centering and digitizing ▪ A video surveillance system of readings ▪ The possibility of using an automated extrapolation chamber as part of the installation to reproduce the absorbed dose (absorbed dose rate) of beta radiation in the tissue ▪ Measurement of ionization currents from 1 fA when using an extrapolation chamber and a precision electrometer ▪ Software for installation operation, calibration and calculations ▪ An alarm and blocking system, control of photon radiation levels in the measurement room and operator room

Purpose: provision of connected equipment with constant voltage; conversion of the RS-485 interface to USB (version 01 only) data transmission via the RS-485 interface (version 02 only).

Purpose: to provide bidirectional data exchange with individual dosimeters DKG-05D, DVS-02D.